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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q4981999-09-10010 September 1999 Proposed Tech Specs Clarifying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits & Adding Ref to Caldon TR for LEFM ML20211G3221999-08-26026 August 1999 Proposed Tech Specs 4.0.6 Re SG Surveillance Requirements ML20212H0771999-08-20020 August 1999 Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820. Page 119 in Unit 1 ASME Section XI of Incoming Submittal Not Included ML20212G0821999-08-20020 August 1999 Rev 4 to Augmented Inservice Insp Plan for Cpses,Unit 1 ML20210R7091999-08-13013 August 1999 Revised Proposed Tech Specs for LAR 98-010,proposing Rev to TS Table 3.3.1-1, Rt Sys Instrumentation & TS Table B 3.3.1-1, Rt Sys Setpoints ML20211M0041999-08-0505 August 1999 Rev 31 to Technical Requirements Manual ML20211G7401999-07-27027 July 1999 Revs 29 & 30 to Technical Requirements Manual (TRM) for Cpses,Units 1 & 2 ML20209E1861999-07-0909 July 1999 Proposed Tech Specs,Adding Reactor Core Safety Limit Figures to Section 5.6.5 of Ts,Clarifying That Overpower N-16 Setpoint Remains in TS & Reflecting NRC Approval of TRs Used to Determine Core Operating Limits Presented in COLR ML20212J4251999-06-23023 June 1999 Proposed Tech Specs,Revising EDG Start Be Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5401999-06-0404 June 1999 Proposed Tech Specs Pages 3.2-6,3.4-24,3.4-25,3.7-23,3.7-30, 3.8-25,3.9-9,3.9-10 & 4.0-2,provided as Addl Aditorial Changes Supplementing LAR 99-001 ML20195B6461999-05-27027 May 1999 Marked-up TS Pages Re LAR 99-004,changing Plant Battery Surveillance ML20195B6771999-05-24024 May 1999 Proposed Tech Specs Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206G7111999-05-0404 May 1999 Proposed Tech Specs Revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections ML20206Q0311999-04-16016 April 1999 Rev 28 to CPSES Technical Requirements Manual ML20205Q1681999-04-14014 April 1999 Rev 27 to CPSES Technical Requirements Manual ML20207F3511999-02-25025 February 1999 Fire Endurance Test to Qualify Protective Envelope for Class IE Electrical Circuits ML20203B0011999-01-25025 January 1999 Rev 10 to Security Training & Qualification Plan ML20211C1071999-01-15015 January 1999 Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval ML20198J3171998-12-21021 December 1998 Proposed Tech Specs,Proposing Changes Administratively for Unit 1 & Increasing Licensed Power for Operation of Unit 2 to 3445 Mwt ML20198J2541998-12-18018 December 1998 Proposed Tech Specs Sections 1.0,3.1,3.3,3.4,3.6,3.7,3.9 & 5.0,converting to ITS ML20198J5211998-12-17017 December 1998 Corrected Tech Specs Pages for Section 3.8 to 971211 Submittal Re TS Conversion Application ML20197K0491998-12-11011 December 1998 Proposed Tech Specs Section 3.8, Electrical Power Systems, Converting to ITS ML20196C5361998-11-20020 November 1998 Proposed TS Converting to ITS Sections 4.0,3.4 & 3.6 ML20195F1751998-11-13013 November 1998 Proposed Tech Specs,Revising Administrative Controls Section to Include Configuration Risk Mgt Program Into CPSES TS ML20195F5291998-11-11011 November 1998 Proposed Tech Specs Revising Core Safety Limit Curves & Overtemperature N-16 Reactor Trip Setpoints for Unit 2 Cycle 5 ML20196B8811998-10-30030 October 1998 Proposed Tech Specs Section 3.3 Re Instrumentation ML20154R7861998-10-21021 October 1998 Proposed Tech Specs Section 3.7, Plant Systems ML20154S2901998-10-14014 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Control,Respectively ML20154C9101998-10-0202 October 1998 Proposed Tech Specs 4.0.6, SG SR, Adding Definitions Required for F* Alternate Plugging Criterion & Identifies Portion of Tube Subject to Criteria ML20153E2661998-09-24024 September 1998 Proposed Improved Tech Specs Sections 3.4, RCS & 5.0, Administrative Controls ML20237E8461998-08-28028 August 1998 Proposed Tech Specs Pages Re Sections 1.0,2.0 & 3.0 of Proposed TS Changes in 980707 & s,In Response to NRC RAI ML20154C4511998-07-20020 July 1998 Interim Change Request ISI-1R5-01, Unit 1 ISI Plan,Rev 5 ML20236T9931998-07-20020 July 1998 1RF06 ISI Summary Rept First Interval,Third Period,First Outage for CPSES Unit 1, Commerical Operating Date 900830 ML20236J3131998-07-0101 July 1998 Revised Proposed Tech Specs Pages Re Safety Injection Signal & Blackout Signal ML20249C6101998-06-22022 June 1998 Proposed Tech Specs Section 3.6 Re Conversion Application ML20216B2811998-04-24024 April 1998 Rev 13 to Cpses,Units 1 & 2,IST Plan for Pumps & Valves First Interval ML20216E6291998-04-0909 April 1998 Marked-up TS Pages,Reflecting Proposed Changes in Amends to Licenses NPF-87 & NPF-89 ML20216B1471998-04-0606 April 1998 Proposed Tech Specs,Allowing Plant to Continue to Operate W/O Having to Perform Portions of SRs ML20217A3901998-03-18018 March 1998 Proposed Tech Specs Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power Re Enforcement Discretion ML20216H1361998-03-13013 March 1998 Proposed Tech Specs Re Electrical Systems Surveillance Requirements ML20248L3191998-03-12012 March 1998 Proposed Tech Specs TS 4.8.1.1.2f.4)b) & TS 4.8.1.1.2f.6)b) Re Request for Enforcement Discretion ML20216D6021998-03-0909 March 1998 Proposed Tech Specs Temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a),for Unit 2 Only ML20203K8621998-02-27027 February 1998 Proposed Tech Specs,Increasing RWST low-low Level Setpoint ML20203J5211998-02-25025 February 1998 Proposed Tech Specs Page to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements 4.8.1.1.2f.4(a) & 4.8.1.1.2f.7(a) Until Plant Startup Subsequent to Next Refueling Outage ML20203J6151998-02-24024 February 1998 Rev 26 to Technical Requirements Manual ML20217P1531998-02-12012 February 1998 Rev 2 to ISI-2R2-01, Unit 2 ISI Plan ML20202B1641998-02-0505 February 1998 Proposed Tech Specs Bases 3/4.7.1.5 Re Main Steam Line Isolation Valves ML20217P2961998-01-30030 January 1998 Rev 5 to Unit 1 ISI Program Plan ML20202E5981997-11-25025 November 1997 Rev 12 to CPSES Units 1 & 2 IST Testing Plan for Pumps & Valves,First Interval ML20212C3881997-10-24024 October 1997 Proposed Tech Specs Re Revised Core Safety Limit Curves & Revised Overtemperature N-16 Reactor Trip Setpoints 1999-09-10
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20212H0771999-08-20020 August 1999 Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820. Page 119 in Unit 1 ASME Section XI of Incoming Submittal Not Included ML20212G0821999-08-20020 August 1999 Rev 4 to Augmented Inservice Insp Plan for Cpses,Unit 1 ML20211M0041999-08-0505 August 1999 Rev 31 to Technical Requirements Manual ML20211G7401999-07-27027 July 1999 Revs 29 & 30 to Technical Requirements Manual (TRM) for Cpses,Units 1 & 2 ML20206Q0311999-04-16016 April 1999 Rev 28 to CPSES Technical Requirements Manual ML20205Q1681999-04-14014 April 1999 Rev 27 to CPSES Technical Requirements Manual ML20203B0011999-01-25025 January 1999 Rev 10 to Security Training & Qualification Plan ML20211C1071999-01-15015 January 1999 Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval ML20154C4511998-07-20020 July 1998 Interim Change Request ISI-1R5-01, Unit 1 ISI Plan,Rev 5 ML20236T9931998-07-20020 July 1998 1RF06 ISI Summary Rept First Interval,Third Period,First Outage for CPSES Unit 1, Commerical Operating Date 900830 ML20216B2811998-04-24024 April 1998 Rev 13 to Cpses,Units 1 & 2,IST Plan for Pumps & Valves First Interval ML20203J6151998-02-24024 February 1998 Rev 26 to Technical Requirements Manual ML20217P1531998-02-12012 February 1998 Rev 2 to ISI-2R2-01, Unit 2 ISI Plan ML20217P2961998-01-30030 January 1998 Rev 5 to Unit 1 ISI Program Plan ML20202E5981997-11-25025 November 1997 Rev 12 to CPSES Units 1 & 2 IST Testing Plan for Pumps & Valves,First Interval ML20212E9811997-10-0606 October 1997 Rev 11 to CPSES Units 1 & 2 IST Plan for Pumps & Valves First Interval ML20210S3911997-09-0303 September 1997 Rev 10 to CPSES Units 1 & 2 Inservice Testing Plan for Pumps & Valves in First Interval ML20151L1391997-07-31031 July 1997 5 to Technical Requirements Manual, for Plant ML20141E6201997-06-26026 June 1997 Rev 24 of CPSES Units 1 & 2 Technical Requirements Manual ML20141F8471997-06-26026 June 1997 Rev 9 to IST Plan for Pumps & Valves First Interval ML20136G4361997-03-13013 March 1997 Rev 23 to CPSES Units 1 & 2 Technical Requirements Manual ML20135A8241997-02-24024 February 1997 Rev 22 to CPSES Units 1 & 2 Technical Requirements Manual ML20134C6831997-01-31031 January 1997 Rev 8 to Comanche Peak Steam Electric Station Units 1 & 2 Inservice Testing Plan for Pumps & Valves First Interval ML20134M4371996-11-13013 November 1996 Self Assessment Guide Program Guidelines ML20129A5991996-10-16016 October 1996 Rev 7 to CPSES Unit 1 & 2 IST Plan for Pumps & Valves First Interval ML20128G7661996-10-0202 October 1996 CPSES Unit 1 & 2 Inservice Testing Plan for Pumps & Valves First Interval ML20138B5181996-10-0101 October 1996 Rev 14 to ODCM for TU Electric CPSES Units 1 & 2 ML20117C8461996-07-19019 July 1996 Glen Rose,Tx ASME Section XI ISI Program Plan,Unit 1 - 1st Interval Rev 4 ML20217M1691996-05-24024 May 1996 Rev 3 to STA-750, Check Valve Reliability Program ML20117C6181996-05-0303 May 1996 Rev 1 to Unit 2 ISI Plan ML20117C6141996-04-14014 April 1996 Rev 1 to Unit 2 ISI Plan ML20107J0941996-04-0202 April 1996 Rev 1 to Interim Change Request ISI-2, CPSES Unit 2 ASME Section XI ISI Program Plan ML20107E4471996-02-0909 February 1996 Rev 1 of CPSES ASME XI ISI Program Plan Unit 2 ML20100B9471996-01-24024 January 1996 Rev 21 of CPSES Units 1 & 2 Technical Requirements Manual ML20086C5491995-06-30030 June 1995 Rev 20 to Technical Requirements Manual ML20091L1941995-03-29029 March 1995 Interim Change Request ISI-IR3-003, Unit 1 ISI Plan ML20081F1131995-03-12012 March 1995 Interim Change Request ISI-1R3-02 to Rev 3 to Unit 1 ISI Plan ML20080Q3351995-02-24024 February 1995 Rev 17 to CPSES Technical Requirements Manual ML20078R6371995-02-15015 February 1995 Rev 5 to CPSES Unit 1 & 2 IST Plan for Pumps & Valves First Interval ML20078H8501994-11-30030 November 1994 CPSES Odmc Rev Change Sheet ML20073L6591994-10-0606 October 1994 Rev 4 to CPSES Unit 1 & 2 IST Plan for Pumps & Valves First Interval ML20072C7081994-07-24024 July 1994 Rev 16 to Simulator Operations/Maint Instruction - 010, Simulator Certification Testing ML20069E5171994-05-17017 May 1994 Interim Change Request ISI-2RO-001, Comanche Peak Ses Unit 2 ISI Program Plan ML20029D0711994-05-11011 May 1994 Rev 16 to Technical Requirements Manual. ML20065K1721994-04-15015 April 1994 Rev 15 to CPSES Units 1 & 2 Technical Requirements Manual ML20058E3841993-11-30030 November 1993 Rev 14 to Technical Requirements Manual, Page 2-27, Clarifying Discussion in Table 2.1.1 Notations for Local Test Connections,Vent & Drain Valves & Revising List of Effective Pages EPL-1 Through EPL-4 ML20058C4441993-11-23023 November 1993 IST Plan for Pumps & Valves First Interval, Rev 3 ML20058B5791993-11-19019 November 1993 Rev 14 to Comanche Peak Steam Electric Station Technical Requirements Manual ML20058J9711993-11-19019 November 1993 Interim Change Request ISI-1R2-005 to Rev 2 to Unit 1 ISI Plan ML20056D8161993-08-11011 August 1993 Salp,Directive 8.6 1999-08-05
[Table view] |
Text
C da ca Evclusti:n DRAFT: B
- Ofcty Significznca Revision
- 0 02/28/85 Page 1 of 4 l 1.0 PURPOSE -
l This Guide provides a description of an acceptable manner for i Review Team Leaders (RTLs) to conduct and document the safety significance evaluations that are required by the CPRT Program Plan.
2.0 PROGRAM PLAN REQUIREMENTS Thef[211ovingisasummaryoftherequirementscontainedinthe Program Plan concerning evaluation of safety significance. This summary provides general background information for this Guide and l does not modify or replace the requirements in the Program Plan. !
The Program Plan requires an evaluation of the safety significance 8 of identified deficiencies. As used in this context, " identified a deficiencies" includes those identified by the NRC-TRT in their ,
definition of the item and shown to be deficiencies after !
investigation by the CPRT and those identified by the CPRT in the conduct of Action Plans. The deficiencies covered by this requirement include specific technical deficiencies and generic /prograc:matic deficiencies. In the case of specific technical deficiencies the evaluation of safety significance aids ,
in the development of approprince corrective action. For generic l or programmatic deficiencies the evaluation of safet/ significance not only facilitates the definition of appropriate corrective action but also facilitates the definition of appropriate expanded i reviews. In either casa the objective of an evaluation of safety significance is the determination of the extent to which the i deficiency would have affected the functioning of the system, i structure, or component in which the deficiency exists. The evaluation of safety significance serves as an input to the evaluation of collective significance. The results of the evaluations of safety significance are to be documented in the Action Plan Results Report.
3.0 REPORTABILITY The evaluation of safety significance is not intended to determine whether a det'iciency must be reported to the NRC. Determination of the reportability of identified deficiencies is the responsibility of TUCCO. The criteria for determining whether a deficiency has i safety significance is different from the criteria used for reportability under 10CFR 50.55(e).
4.0 CRITERIA FOR SAFLTY SIGNIFICANCE For the purposes of the CPRT a deficiency is considered significant i if after evaluation any of the following conditions are met: '
The uncorrected condition would have resulted in a violation of a Technical Specification for any mode of operation.
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Cuida cn Evclustian DRAFT: B cf Scfcty Significcnco R vision: 0 02/28/85 Page 4 of 4 j 6.0 COMPARISON AGAINST REPORTABILITY REQUIREMENTS - (Cont'd) .
A significant deviation from performance specifications which will require extensive evaluation, extensive redesign, or extensive evaluation, extensive redesign, or extensive repair to establish the adequacy of a structure, system, or component to meet the criteria and bases stated in the safety analysis report or construction permit or to otherwise establish the adequacy of the structure, system, or component to perform its
, intended safety function.
The above bases are not the bases for safety significance determinations, but only for reportability.
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Cuida en Ev:1uatian DRAFT: B cf Scf0ty Significenen Revision: 0 02/28/85 Page 2'of 4 4.0 CRITERIA FOR SAFETY SIGNIFICANCE - (Cont'd) -
The uncorrected condition would have resulted in the failure of a system, structure, or component important to safety to function when and as required.
The uncorrected condition would have resulted in a system, structure, or component important to safety that fails to meet its design bases as stated in the FSAR such that physical rework, repair or replacement is required.
The uncorrectef condition would have resulted in a violation of the requi. ments of 10CFR related to the functioning of systems, structures, or components important to safety.
5.0 EVALUATION OF DEFICIENCIES Each identified deficiency should be evaluated with respect to its safety significance. In making this assessment Review Team Leaders should consider:
The function of the system, structure, or component in which the deficiency exists.
Whether alternative systems, structures, or components exist
, that would achieve the required safety function.
Whether the deficier.cy results in a significant increase in the probability of occurrence or the consequences of an accident or malfunction evaluated in the FSAR.
Whether the deficiency results in the possibility of an accident or malfunction different from those evaluated in the FSAR.
Whether the deficiency results in a significant reduction in the margins of safety associated with any technical specification.
Whether planned reviews or tests would have found the deficiency prior to the time at which the system, structure, or component would have been required to perform its safety function.
If the deficiency is generic or programmatic in nature, whether the deficiency resulted in a combination of component level functional defects that, taken together, reduce the degree of protection afforded the public.
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Each evaluation should define the deficiency in detail and state whether the evaluation is of the specific deficiency, a generic or programmatic deficiency, or both. The evaluation should use the above list of factors plus any others determined by the Review Team Leader to be appropriate to characterize the deficiency. The comparison against these factors should be documented. Based upon this comparison the evaluation should document a determination of
. the safety significance of the deficiency relative to the criteria in Section 4.0 of this Guide.
6.0 COMPARISON AGAINST REPORTABILITY REQUIREMENTS As noted in Section 3.0 above, this Guide does not address reportability requirements and it is not the responsibility of the CPRT to make the determination of the reportability of any deficiency. However, it is useful for Review Team Leaders to recognize the difference between the safety significance evaluation and the reportability requirements of 50.55(e). Items may be reportable under 50.55(e) without being safety significant under the CPRT Program Plan. For example an approved design for a component may not conform to one or more criteria contained in the FSAR, but the component may still be capable of performing its safety functions based upon an evaluation. In such a case the t deficiency may be reportable but would not have safety significance. Another example could be a breakdown in QA such as in the inspection program that is evaluated not to have involved attributes important to system, structure, or component functions.
Again this may be reportable, but would not have safety significance.
For information only, the following are the bases listed in 10CFR 50.55(e) for repcreability:
A significant breakdown in any portion of the quality assurance program conducted in accordance with the requirements of Appendix B to this part; or A significant deficiency in final design as approved and released for construction such that the design does not conform to the criteria and bases stated in the safety analysis report or construction permit; or A significant deficiency in construction of or significant damage to a structure, system, or component which will require extensive evaluation, extensive redesign, or extensive repair to meet the criteria and bases stated in the safety analysis report or construction permit or to otherwise establish the adequacy of the structure, system, or component to perform its intended safety function; or
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t OFFICE MEMORANDUM TO: Review Team Leaders FROM:
Jenior Review Team DATE: January 30, 1985
SUBJECT:
Guide for Safety Significance Evaluations Attached is a guide for performing evaluations of safety significance when rcquired by the Program Plan. The Senior Review Team has reviewed this guide cnd determined that its use will satisfy Program Plan requirements. Review Team Leaders may use alternative methods of meeting Program Plan requirements.
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